高温堆临界实验装置ASTRA的初始临界计算

• 作 者: 常鸿 杨永伟 经荥清
• 机 构: 清华大学核能与新能源技术研究院,清华大学核能与新能源技术研究院,清华大学核能与新能源技术研究院 北京100084,北京100084,北京100084
• 出 处: 清华大学学报(自然科学版)
• 发表日期: 2006年06期
• 关键词: 球床式高温气冷堆 初始临界 TRIPOLI-4.3程序

为了验证球床式高温气冷堆初始临界的计算方法,用法国M on te C arlo程序TR IPOL I-4.3对燃料球内的包覆燃料颗粒以及堆芯内不同的球分布进行了模拟。考虑了燃料球的双重非均匀性、不同区域内球的布置以及其在堆芯的体积填充率等。计算了俄罗斯的球床式高温气冷堆临界试验装置A STRA的初始临界。与实验结果比较,计算得到的临界实验高度误差为0.6%,堆芯有效增值因子keff误差为0.1%。TR IPOL I-4.3程序是球床式高温气冷堆初始临界计算的有效工具。

In order to validate the initial critical calculation for a ball-point HTR reactor, the coated fuel pellets in the fuel pellet and the different ball distributions in the core were simulated using TRIPOL I-4.3 from the French Thermal Clover program. The double heterogeneity of the fuel ball, the arrangement of the ball in different regions and the volume filling rate in the core are considered. The initial criticality of A STRA, a critical ballistic HTR reactor in Russia, was calculated. Compared with the experimental results, the calculated critical experiment height error is 0.6% and the core effective value-added factor keff error is 0.1%. The TR IPOL I-4.3 program is an effective tool for the initial critical calculation of ball-point HTGRs.